Abstract
The studies relate to refueling schemes in the radial blanket of the large fast breeder reactor. The reactor adopted for these studies is a 1,000 MWe sodium cooled, mixed plutonium-uranium oxide fuel unit with a thermal rating of 2,400 MW. Burn-up calculations, combined with different refueling schemes are carried out to determine its characteristics. From the results obtained on power distribution, the coolant flow rates in the core and in the different blanket layers are calculated under the condition of limited cladding temperature. The different refueling schemes are then compared mainly from the standpoint of the the thermal performance of the reactor.
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